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  • Welcome
  • Background
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  • Projects
    • Candidate Materials Evaluation for the Supercritical Water-Cooled Reactor
    • A Mechanistic Basis for Irradiation Assisted Stress Corrosion Cracking
    • Accelerator-Based Study of Irradiation Creep of Pyrolytic Carbon Used in TRISO Fuel Particles for Very High Temperature Reactors (VHTR)
    • Acquisition of a Research Grade Ion Implanter for Research and Education in Ion Beam Modification of Materials
    • Alloys for 1000°C Service in the Next Generation Nuclear Plant
    • BWRVIP Highly Irradiated Stainless Steel Crack Growth
    • Consortium on Cladding and Structural Materials for Advanced Nuclear Energy Systems
    • Constant Extension Rate Testing of Alloy 690 in Supercritical Water
    • High Temperature Materials for the Gas-Cooled Fast Reactor
    • Localized Deformation as a Primary Cause of Irradiation Assisted Stress Corrosion Cracking
    • Radiation-Induced Segregation and Phase Stability in Candidate Alloys for the Advanced Burner Reactor
    • Stress Corrosion Cracking and Corrosion of Candidate Alloys for the Supercritical Water Reactor Concept
    • Stress Corrosion Cracking of Neutron Irradiated Cast Stainless Steels in High Temperature Water
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Posted on July 15, 2013 (June 22, 2021) by Michigan Engineering

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Gary Was

Gary Was

gsw@umich.edu

(734) 763-4675

1911 Cooley

Radiation Materials Science Research Group

Michigan Engineering

1221 Beal Ave. Ann Arbor, MI 48109-2102

+1 (734) 647-7000

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